05000324/LER-2017-001, Regarding Speed and Frequency Oscillations Result in Inoperable Emergency Diesel Generator
| ML17081A236 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/22/2017 |
| From: | William Gideon Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 17-0022 LER 17-001-00 | |
| Download: ML17081A236 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 3242017001R00 - NRC Website | |
text
t$1f,_ DUKE William R.Gkieon ENERG Brunswick Nuclear Plant
RD. Box10429 Southport, NC 28461 0: 910.457.3698 MAR 2 2 2017 10 CFR 50.73 Serial: BSEP 17-0022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Licensee Event Report 1-2017-001 In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Duke Energy Progress, LLC, submits the enclosed Licensee Event Report (LER). This report is being submitted in response to a Severity Level IV violation received in NRC Inspection Report 201 6-004, dated February 9, 201 7 (ADAMS Accession Number ML1 7041 AOl 0), for failure to provide a written report to the NRC within 60 days of identifying a condition which was prohibited by plant Technical Specifications. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager Regulatory Affairs, at (91 0) 457-2487.
Sincerely, William R. Gideon SWR/swr Enclosure: Licensee Event Report 1-2017-001
U.S. Nuclear Regulatory Commission Page 2 of 2 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net
NRC FORM 366 (06-2016)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (06-2016)
LICENSEE EVENT REPORT (LER)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Brunswick Steam Electric Plant (BSEP) Unit 1
- 2. DOCKET NUMBER 05000325
- 3. PAGE 1 OF 5
- 4. TITLE Speed and Frequency Oscillations Result in Inoperable Emergency Diesel Generator
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACILITY NAME Brunswick Unit 2 DOCKET NUMBER 05000324 02 07 2016 2017 - 001
- - 00 03 22 2017 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)
- 10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(4) 088 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 73.77(a)(1) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 73.77(a)(2)(i) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 73.77(a)(2)(ii) 50.73(a)(2)(i)(C)
OTHER Specify in Abstract below or in Page 5 of 5 LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET
Safety Assessment
Speed and frequency oscillations in EDG-1 were first observed during a LOOP event on February 7, 2016, when emergency busses E1 and E2 were being powered by EDG-1 and EDG-2. Only EDG-1 exhibited oscillations. The two EDGs supply power to independent buses and therefore do not affect each other. The magnitude of the oscillations on EDG-1 was observed to be between 59.7 Hz and 60.5 Hz, which was well within the bounds of TS Surveillance Requirement 3.8.1.2 of greater than or equal to 58.8 Hz and less than or equal to 61.2 Hz. EDG-1 successfully powered all required loads during the actual LOOP event, up to a peak loading during the event of 2650 KW. No intervention by operators was needed at any time to control the oscillations or to protect any equipment powered by EDG-1. During the LOOP/LOCA test conducted on March 2, 2016, the loading on the bus was approximately the same as that experienced during the actual LOOP event of February 7, 2016. Nonetheless, the magnitude of the oscillations remained approximately +/-0.4 Hz and remained within a peak power value of approximately 2840 KW. By comparison, the EDG is designed for continuous operation at a maximum of 3500 KW, and for up to 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> of operation at 3850 KW. Consequently, safe operating limits for EDG-1 were never challenged, and EDG-1 was shown by both testing and an actual event response to be capable of powering loads expected in the event of an LOOP/LOCA event. In the event that an additional source of standby onsite alternating current (AC) power had been needed, the sites supplemental emergency diesel generator was available throughout the entire event.
Based on this analysis, this event had no adverse impact on the health and safety of the public.
Corrective Actions
The governor for EDG-1 was replaced on March 6, 2016, as part of a planned upgrade. The governor system replacement included in its scope all of the speed control components and connections which are suspected of being capable of producing the oscillations that were observed. Since the oscillations have not recurred since that time, it is concluded that the source of the control instability has been eliminated by the replacement and no further corrective actions are planned.
Previous Similar Events
No events have occurred in the past three years in which an emergency diesel generator was made inoperable because of a problem with its governor system.
Commitments
This report contains no new regulatory commitments.